Overview of Activities for the Wendelstein 7-X Scraper Element Collaboration

被引:0
作者
Lumsdaine, A. [1 ]
Bjorholm, T. [1 ]
Harris, J. [1 ]
McGinnis, D. [1 ]
Lore, J. D. [1 ]
Fellinger, J. [2 ]
Hoelbe, H. [2 ]
Boscary, J. [3 ]
Tretter, J. [3 ]
Neilson, H. [4 ]
Titus, P. [4 ]
Clark, E. [5 ]
Ekici, K. [5 ]
Wurden, G. [6 ]
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37830 USA
[2] Max Planck Inst Plasma Phys, Greifswald, Germany
[3] Max Planck Inst Plasma Phys, Garching, Germany
[4] Princeton Plasma Phys Lab, Princeton, NJ USA
[5] Univ Tennessee, Knoxville, TN USA
[6] Los Alamos Natl Lab, Los Alamos, NM USA
来源
2015 IEEE 26TH SYMPOSIUM ON FUSION ENGINEERING (SOFE) | 2015年
关键词
Wendelstein; 7X; divertor; high heat -flux; modeling and simulation; DESIGN;
D O I
暂无
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The Wendelstein 7-X (W7-X) stellarator is in final stages of commissioning, and will begin operation in the last half of 2015. In this first phase the machine will operate with a limiter, and will be restricted to low power and short pulse. But in 2019, plans are for an actively cooled divertor to be installed, and the machine will operate in steady-state at full power. Recently, plasma simulations have indicated that, in this final operational phase, a bootstrap current may evolve in certain scenarios. This will cause the sensitive ends of the divertor target to be overloaded beyond their qualified limit. A high heat flux scraper element (HHF-SE) has been proposed in order to take up some of the convective flux and reduce the load on the divertor. In order to examine whether the HHF-SE will be able to effectively reduce the plasma flux in the divertor region of concern, and to determine how the pumping effectiveness will be affected by such a component, it is planned to include a test divertor unit scraper element (TDU-SE) in 2017 during an earlier operational phase. Several US fusion energy science laboratories have been involved in the design, analysis (structural and thermal finite element, as well as computational fluid dynamics), plasma simulation, planning, prototyping, and diagnostic development around the scraper element program (both TDU-SE and HHF-SE). This paper presents an overview of all of these activities, and their current status.
引用
收藏
页数:8
相关论文
共 17 条
[1]  
Boscary J., FUS ENG DES IN PRESS
[2]   Technical challenges in the construction of the steady-state stellarator Wendelstein 7-X [J].
Bosch, H. -S. ;
Wolf, R. C. ;
Andreeva, T. ;
Baldzuhn, J. ;
Birus, D. ;
Bluhm, T. ;
Braeuer, T. ;
Braune, H. ;
Bykov, V. ;
Cardella, A. ;
Durodie, F. ;
Endler, M. ;
Erckmann, V. ;
Gantenbein, G. ;
Hartmann, D. ;
Hathiramani, D. ;
Heimann, P. ;
Heinemann, B. ;
Hennig, C. ;
Hirsch, M. ;
Holtum, D. ;
Jagielski, J. ;
Jelonnek, J. ;
Kasparek, W. ;
Klinger, T. ;
Koenig, R. ;
Kornejew, P. ;
Kroiss, H. ;
Krom, J. G. ;
Kuehner, G. ;
Laqua, H. ;
Laqua, H. P. ;
Lechte, C. ;
Lewerentz, M. ;
Maier, J. ;
McNeely, P. ;
Messiaen, A. ;
Michel, G. ;
Ongena, J. ;
Peacock, A. ;
Pedersen, T. S. ;
Riedl, R. ;
Riemann, H. ;
Rong, P. ;
Rust, N. ;
Schacht, J. ;
Schauer, F. ;
Schroeder, R. ;
Schweer, B. ;
Spring, A. .
NUCLEAR FUSION, 2013, 53 (12)
[3]  
Clark E., FUSION SCI IN PRESS
[4]   PIES free boundary stellarator equilibria with improved initial conditions [J].
Drevlak, M ;
Monticello, D ;
Reiman, A .
NUCLEAR FUSION, 2005, 45 (07) :731-740
[5]   Aspects of steady-state operation of the Wendelstein 7-X stellarator [J].
Geiger, J. ;
Wolf, R. C. ;
Beidler, C. ;
Cardella, A. ;
Chlechowitz, E. ;
Erckmann, V. ;
Gantenbein, G. ;
Hathiramani, D. ;
Hirsch, M. ;
Kasparek, W. ;
Kisslinger, J. ;
Koenig, R. ;
Kornejew, P. ;
Laqua, H. P. ;
Lechte, C. ;
Lore, J. ;
Lumsdaine, A. ;
Maassberg, H. ;
Marushchenko, N. B. ;
Michel, G. ;
Otte, M. ;
Peacock, A. ;
Pedersen, T. Sunn ;
Thumm, M. ;
Turkin, Y. ;
Werner, A. ;
Zhang, D. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2013, 55 (01)
[6]   Design, performance and construction of a 2 MW ion beam test facility for plasma facing components [J].
Greuner, H ;
Bolt, H ;
Böswirth, B ;
Franke, T ;
McNeely, P ;
Obermayer, S ;
Rust, N ;
Süss, R .
FUSION ENGINEERING AND DESIGN, 2005, 75-79 :345-350
[7]  
Hirshman S.P., 1986, COMP PHYS COMMUN, V43
[8]   STEEPEST-DESCENT MOMENT METHOD FOR 3-DIMENSIONAL MAGNETOHYDRODYNAMIC EQUILIBRIA [J].
HIRSHMAN, SP ;
WHITSON, JC .
PHYSICS OF FLUIDS, 1983, 26 (12) :3553-3568
[9]  
Holbe H., 2014, NUCL FUSION UNPUB
[10]  
Lore J., 2012, P 24 IAEA FUS EN C S